ML20034A201
| ML20034A201 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 04/09/1990 |
| From: | Silady J COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| 0649T, 649T, GL-88-16, NUDOCS 9004200412 | |
| Download: ML20034A201 (22) | |
Text
!-
[^ ) 1400 Opus Place Commonwealth Edloon I
'7 Downers Crove, Illinois 60515
\\
v April 9, 1990 Dr. Thomas E. Murley, Director Offlee Nuclear Reactor Regulation U.S. Nuclear Reguintory Commission Washington, DC 20$$$
Attentiont U.S. NRC Document Control Desk
Subject:
Quad Cities Nuclear Power Station Unit 2 Cycle 11 Reload and Core Operating Limits Report HEC Docket Nos. 50-265 Referencess (a) Letter from J.A. Silady to T.E. Murley, submitting proposed amendment to remove Cycle-Specific Core Limits from the Quad Cities Technical Specifications, dated July 11, 1989.
(b) Letter from T.M. Ross to T.J. Kovach dated October 20, 1989 providing NRC approval and SER on Quad Cities Amendments 120 and 116 for Units 1 and 2, respectively.
(c) Letter from J.A. Silady to T.E. Murley dated January 15, 1990 submitting proposed amendment to Unit 2 MCPR limit to reflect use of NRC approved fitel type CE8X8NB.
Dr. Murley Quad Cities Unit 2, which has comp 13ted its tenth cycle of operation, is currently preparing for Cycle 11 startup. The purpose of this letter is twofoldt (1) to advise you of the Commonwealth Edison Company (CE00) review and approval of the Cycle 11 reload under the provisions of 10 CFR 50.59, and (2) to transmit the Core Operating Limits Reports (COLR) for the upcoming cycle consistent with Generic Letter 88-16. Note that the necessary Technical Specification changes to incorporate the COLP were proposed in the Reference (a) submittal and approved in the Reference (b) NRC letter and SER.
i The Quad Cities Unit 2 Cycle 11. core consists of HEC approved fuel designs and was designed to operate under currently approved fuel design parameters, Technical Specifications, and related bases such thatt i
- 1) Core operating characteristics will be less limiting than those previously reviewed and accepted; or
.g2[M 5
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!!r. T.E. Murley April 9, 1990
- 2) For those postulated incidents analyzed and reported in the Final i
Safety Analysis Report (FSAR) which could potentially be affected i
by the fuel reload, a re-analysis using NRC-approved methods has demonstrated that the results of the postulated events are within allowable limits.
Conanonwealth Edison has performed a detailed review of the relevant licensing documents, the bases, and references. Based on the review, a safety evaluation was prepared as required by 10 CFR 50.59 (a) and (b) and submitted to on-Site and Off-Site Review. As in the past, the reload licensing analyses were performed using NRC approved methodologies as reported in the FSAR, i
NEDE-24011 (CESTAR) and other generically approved documents.
Eaison has reviewed the cycle-specific licensing results and concluded that additional Technical Specification changes are not required for Cycle 11 operation at Quad Cities Unit 2 provided that the Reference (c) preparatory amendment receives NRC approval.
Furthermore, Edison has completed On-Site and Off-Site Reviews which determined that no unreviewed safety questions are created by the reload.
Following completion of these On-Site and Off-Site Reviews, Ceco received NRC Bulletin 95-02, which discusses the impact of channel bow on thermal margin. As required by the Bulletin, CECO will account for the
~
effects of channel bow during Quad Cities Unit 2 Cycle 11 operation and all subsequent relt, ads.
Details will be provided in the Bulletin response, which will be submitted approximately April 23, 1990.
Therefore, application for an amendment to the Quad Cities Unit 2 operating Ilcense is not required for resumption of operation with the Cycle r
11 reload core. The estimated startup is April 29, 1990.
If there are any further questions regarding this matter, please contact this office.
Very truly yours, 4-ohn A. Silady Nuclear Licensing Administrator Attachment COLR for Quad Cities Unit 2 Cycle 11 cci A.B. Davis - Regional Administrator, R111 L.N. 01shan - Project Manager, NRR T. Taylor - Senior Resident Inspector Quad Cities
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for Unit 2, aaload 10 (cycle n) i
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All All Orierinal T==== Icveda 11) 10/89 P
Quad cities - Unit 2 i
cycle 11
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Care Operstitup Limits Report TAIEE OF Ct2frENIS EMB RE:FERDOS......................................................
iii LT3r OF FI2JREE.................................................
iv 1.0 03 fin 0L noo WrIHI3tAMhL BIDCX INMt.30Bf2RTIW (3.2/4.2)...
1-1 1.1 Teenical specification anferunae................. 1-1 1.2 Description.......................................
1-1 2.0 AVERAGE PIANhR LINEAR HEXP GENDIAl rim RA2E (3.5/4.5).....
2-1 2.1 Technical Specification Referunos.................
2-1 2.2 Description.......................................
2-1 3.0 LINEAR HEXP GENERATIN RA3E (3.5/4.5)..................
3-1 3.1 Te2nical Specification Referunos.................
3-1 3.2 Description 3-1 4.0 MDuMLM cuTICAL IQfER RATIO (3.5/4. 5).................
4-1 4.1 Te&nical specification Referunos.................
4-1 4.2 Description.......................................
4-1 i
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Quad Cities - Unit 2 11 Cycle 11 1
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r Core Operating Limits Report r
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f 1.
o:mmorusalth Edison omgany and Iowa-Illinois Gas ard Electric Docket No. 50-265, Quad Cities Station, Unit 2 Facility Lionnae, Lionnen No. IRP-30.
2.
Istter fztma D. M. Crutzhfield to All Power Remotor Licenses and I
Applicants, Generic Istter 88-16; G.-.ing the Anzwal of Cycle Wfic Parauster Limits frtan 'Duhnical Pifications.
3.
SWemental Reload License sentittal fcr Quad Cities Nuclear Power Staticm, Unit 2, Raload 10 (Cycle 11), 23A6451, Rev. O, May 1989.
4.
Quad Cities Nuclear Power Station, Units 1 and 2,.%FER/GESTR-IFA Iras-of-Cbolant-Arv irtarit Analysis, NEDC-3134SP, June 1987 (as amended).
5.
General Electric Standard Application for Reactor Fual- (GESBR),
NEEE-24011-P-A-9, Septamher 1988 (as amended).
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4 Quad Cities - Unit 2 111 Cycle 11
,,.--,,.,,- ~,,,-
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- - =, - -,., _--
core operating Limits Report 12sT or rimmEE
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FIN Tmrei-~ c.tr11M M
2-1 Navi== Average Planar Linear Heat Genmention Rata 2-2 (MhPDER) vs. Average Planar Pvpnews far Fuel Type P80GB298.
2-2 He'tinum Average Planar Linear Heat Generaticri Rata 2-3 (MhPDER) vs. Average Planar P=s for Fual Types P85tB265N and BP8tEB265H.
2-3 Mavi= = Average Planar Linear Heat Generation Rata 2-4 (MhPUCR) vs. Average Planar Pwe for Fuel Type BMIRB282.
i 2-4 Navi== Average Planar Linear Heat Generaticri Rata-2-5 (MhPUCR) vs. Average Planar _Pws for Fbal Type BP8tRB283H.
2-5 Naviu m Average Planar Linear Heat Generation Rata 2-6 (MkPDER) vs. Average Planar P_we for Fuel Type BP8tRB299.
2-6 Mav4= M Average Planar Linear Heat Generation Rata 2-7 (MAPDER) vs. Average Planar Pwa for fuel Type l
BPSIRB299L.
2-7 Mav4== Average Planar Linear Heat Generation Rata 2-8 (MAPDER) vs. Average Planar Exposma for Fuel Type l
BD316A.
2-8 Mav4== Average Planar Linear Heat Generation Rata 2-9 l
(MAPUCR) vs. Average Planar P_wa for Fual Type BD300C.
2-9 Mav4== Average Planar Linear Heat Generation Rate 2-10 (MhPINGR) vs. Average Planar Pwe for Fuel Type GE9B-PBDWB299-11GZ-80M-145-T.
2-10 Mav4== Average Planar Linear Heat Generation Bata 2-11 (MhPUER) vs. Average Planar Pwe for Fuel Type GE9B-P8tMB310-9GZ-8Gi-145-T.
4-1 Kf Factor vs. Core Flow %.
4-2 Quad Cities - Unit 2 iv Cycle 11
Core Operatirq Limits Report 1.0 CINm0L XD IEENtNdkL BUXX DEriq3ERMLTTEN f 3.2/4.2) 1.1 TE3MICAL SPEC 2HCkTICM REMGMcEr Tactinical Specification Table 3.2-3 and 3.6.H 1.2 MBQtIPTIGir i
Da acd Withdrawl Block Manitar tWie Insertamarcation Trip i
Satpoint for tuo recirculation loop %.iian is datambled frtan the following relationship
$ (0.65)Mi + 434**
f
- clasped, with an allcumble value not to anomad the allowable value for recirculation locp flow (W$) of 1004.
Wd is the peuw.i of drive flow recpired to prtxhaan a rated core flew of 98 millien Ib/hr. Trip level settirq is in i=-d. of rated power (2511 PWth).
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4 Quad cities - Unit 2 1-1 cycle 11 S
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'I Cbre Operating Limits' Report l
2.0~
AVERAGE PIANMt I2NEMt HIDLT GEMEEATICM RATE (APIER) (3.5/4.5) j 2.1 =
TEDMICAL SPE2FIGLTIGi RE3TRENCE:
Tedmiaal Fification 3.5.I
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2.2 IEBCRIPI' ICE:
Iha >vi== Average Planar Linear Hast Generatica Rates (MAPUER)-
versus Average Planar Pwe for fuel tp P80GB298 is astumirud fran Figure 2-1.
'Ihm Mari== Average PJanar Linear Heat Generation Rates (MAPUER) d versus Average Planar Equeurs for fuel types P8tRB265H and c
BF8tRB265H are determined frue Figure 2-2.
~
'Iha Mari== Average Planar Linear Heat Generation Rates (MAPDER) versus Average Planar E-'we for fuel type BPBIRB282 is determined fran Figure 2-3. -
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'Ihn Mavi== Average Planar Linear Heat Generation Rates (MAPUER)'
l Versus Average Planar 5'-'we for fuel type BP8tRB283H is L
determined fran Figure 2-4.
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N Mavi==' Average Planar Linear Heat Generation Rates (MAPU1GR) wesus Average Planar 5'wanwa for fuel type BP8tRB299 is datarmined fran Figure 2-5.
'Ihm Navi== Average Planar Linear Heat Generation Rates (MAPUER) versus Average Planar 5'wa=we for fuel type BP8tRB299L is datarmined fran Figure ~ 2-6.
E
'Iha Mavi== Average Planar. Linear Heat Generation Rates -(MAPIHGR) '
L versus Average Planar 5'wa=?e for fuel type BD316A is determined frur. Figure 2-7.
'Iha Mavi== Average Planar Linear Heat Generation Rates (MAPIHGR)-
versus Average Planar 5'wa=we for fuel type BD300C is deramined fran Figure 2-8.-
'Iha Mavi== Averam Planar Linear. Heat Generation Rates- (MAFIHGR) i versus Average PJamr Expcaure for fuel type GE99-P8DWB299-11GZ-835-145-T is datarmined from Figure 2-9.
'Iha Maximan Average Planar Linear Heat Generation Rates (MAPIER)'
versus Average Planar l'wanwe for fuel type GE9B-P8DWB310-9GZ -
83f-145-T is datamined fran Figure 2-10.
4 Quad Cities - Unit 2 2-1 Cycle 11 J
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- ~l Maximum Average Planar Linear Heat Generation Rate MAPLHGR; vs Average Planar Exposure for Fuel Type P8DGB298
{x 3
1 12m
- x g
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11.50 -
o y11.00 p
N r=
4 se d 10.50
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10.00
_f 9.50 -
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0 5000 10000 15000 20000 25000 30000 35000 40000 Average 'anarixposure 'WWd/S~)
=
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Figure 2-1
Maximum Average Planar Linear Heat Generation Rate (MAPLHGR;
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vs Average P anar Exposure for Fuel Types P8DRB265H and BP80RB265H ia
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r-12.50 i
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12.00 N
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11.50 x
211 i.00=
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9.50 -
9.00 3
8.50
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0 5000 10000 15000 20000 25000 30000 35000 40000 45000 l
Average Planar Exposure {WWd/S[
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Figure 2-2 I
M Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) g B
vs Average Planar Exposure for Fuel Type BP8DRB282 g
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12.50
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g
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1 LOG
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11.50 s
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g IJ.00 1 50 9.00 i
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150 0
5000 10000
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- 1 Figure 2-3
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Maximum Average Planar Linear Heat Generation Rate MAPLHGR; g-
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vs Average Planar Exposure for Fuel Type BP8DRB283H y
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5000 10000 15000 20000
- 25000 M
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Average Planar Exposure 'WWd/S ",
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Figue 2-4 1
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Maximum Average Planar Linear Heat Generation RatelMAPLHGR; y
B.
vs Average Planar Exposure for Fuel Type BP80RB299 w
m R
u.50 ya j
u.00-
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li).00 --
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1 50 l
'}.00 0
5000.
10000 15000 20000 25000 30000 35000 40000 45000 i
Average 'lanar Exposure 'WWd/Sj 1-Figure 2-5
u' Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) g-
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ji vs Average Planar Exposure for Fuel Type BP80RB299L g
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B 12.50 g
12.00--
R
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25=11
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S 10.00
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9.00-0 5000 10000 15000 20000 25000 M
N W
M Average Planar Exposure {WWd/S"c
- i Figure 2-6
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Maximum Average Planar linear Heat Generation Rate (MAPLHGR
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1 s.
vs Average Planar Exposure for FuelType BD316A j
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g
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13.50
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12 5 12 00 11.50 s N 11'00 S' g'50 N
D;0.00 1
IN 9.50-3
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N 8.50
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7.50
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7.oo 6.50-6.00 -
5.50-
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5000 10000 15000 20000 25000 30000 35000 40000 45000 50000 Ayerage 'lanar Exposure i'WWd/S" a
!=i Figure 2-7 1
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Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) c e
vs Average Planar Exposure for Fuel Type BD3000 i
s
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l" re w g
i 12 50 12 00 11~50 N
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g10.50 B_i_ii" N
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.$ 9.00
= 8.50 -
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8.00 7.50-7.00
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6.50 6.00 i
0 5000 10000' 15000 20000 25000 30000 35000 40000 45000 50000 Average anor Exposure [WWd/ST[
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1 Figure 2-8
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e Maximum Average Planar Lineer Heat Generation Rate (MAPLHGR;
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B vs Average Planar Exposure for-Fuel Type 1
GE9B-P8DWB299-11GZ-80M-145-T i
g
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13.50 i
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15 12 00 11'50-11.00 N
e 10.00-v.e5 N
l g 8.50--
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8.00-
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7.50
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6.50
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5.50-0 5000 10000 15000 20000 25000 30000 35000 40000 45000 50000
. Average Planar Exposure 'WWd/S" i,
Figure 2-9
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Maximum Average Planar Linear Heat Generation Rate ;MAPLHGR; e-g 3
vsLAverage Planar Exposure for Fuel Type-i 1
GE9B-P8DWB310-9GZ-80M-145-T i
2 E
13.50 I
13.00 12 50 12.00 11 50-11 00 210 50 D 10.00 E
9.50 -
i S $ 9.00 ~
7 a'
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" 8.50 -
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8.00
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7.00
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6.50
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6.00 5.50 -
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0 5000 10000 15000 20000 25000 30000 35000 40000
- F0 50000 Average Planar Exposure { mwd /ST) 1 Figure 2-10
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-e 3.0-LDG!aR HDLT GENIEULTEM RME (IHEt) f 3. 5/4. 5) 3.1 TEI2MICAL SPECIFIClLTIN
REFERENCE:
N Specification 3.5.J I
3.2 IEBCRIPfICE
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!he INEt limit is 13.4 kW/ft for fuel types:.
1.
P90GB298 1
2.; BF8tRB265H'
.3.~
BP8tRB282-
.4.
BEGIRB283H -
5.=
BPSIMB299H
- 6. - BP8tRB299L-b.
'Iha IIGR limit is 14.4' kw/ft for fuel' types:
1.
50316A
{
2.
BD300C 3.
GE9B-PSDWB299-11GZ-80M-145-T-4.
GE99-PBEMB310-9GZ-8(M-145-T.
l l
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i 4
5 6
4 1
in d
d L
Quad Cities - Unit 2
~3-1 Cycle 11
- . _ _ ut, _
,4 4
'4.0' MINDEM C21TIchL PONER RATID OCPR) (3.5/4.5) 4.1 WChL SPECIFIC &TICH RERRENCE:
Todmioal Fif4=ticri 3.5.K ani 3.6.H 4.2-IESCRIPTICE:
Durirg steady-stata q==t.icri at rated core flow, )CPR shall be greater than or acpal:
1.31 for tave.< 0.68 sec.
1.36 for tava 2 0.86 sec.
t (0.278)tave + 1.121 for 0.68 sec. < tave < 0.86 sec.
'l where tave = mean 20% acram insertion tima for all surveillance data fran Tedt. Spec. 4.3.C which has been generated in the current cycle.
i For oore flows other than rated, these naminal values of MCPR shall be irud by a factor of Kf where Kf is as shown in Figure 4-1.
ition operating with a Feedwater Heater Out-of-servica,- the Operating MGR Limit shall be increased by 0.01.
i 1
1 I
i Quad Cities - Unit 2 4-1 Cycle 11 l
i,.
n KeFACTOR d.
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53 iii m-a 1.50 K
3 1 40 il s
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N AUTOMATIC FLOW CONTROL Kf CEVE r
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9.20
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N NANUAL FLOW CONTROL Kf CWVE ION FLOWMAX N
'N x
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j gg 1
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0.90
-25 30 35 40 45 50-55 60~
65 70 75 80 85 90 -
95 100 Core Flow I 1
Agure 4-1 t
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